TENDL-2015 Nuclear data library
Neutron sub-library for Md (Z=101) and A=260: partial cross sections to discrete levels
Reaction types
Reaction #
260
Md(n,a)
260
Md(n,d)
260
Md(n,g)
260
Md(n,h)
260
Md(n,inl)
260
Md(n,p)
260
Md(n,t)
260
Md(n,a)